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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
G. Stange, H. Yeom, B. Semerau, K. Sridharan, M. Corradini
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 286-301
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16980
Articles are hosted by Taylor and Francis Online.
Pool boiling critical heat flux (CHF) measurements have been performed on stainless steel and zirconium wires in nanofluids consisting of oxide nanoparticles (7 to 250 nm) dispersed in water as well as in high-purity water after coating these wires with a variety of materials and methods. For the nanofluids study, nanoparticles of titania, alumina, zirconia, and yttria-stabilized zirconia (YSZ) were investigated for various sizes and concentrations. Results showed improvements in CHF in the range of 50% to 100%, with titania and zirconia exhibiting the highest and the lowest levels of improvement, respectively. Wires were coated separately with the same oxide nanoparticle materials, as well as pure titanium nanoparticles, using the electrophoretic deposition (EPD) technique and by nanofluid boiling. EPD coatings yielded superior and more consistent improvements in CHF values in clean water, suggesting that this could be a more practical approach than using nanofluids. Coating uniformity plays an important role in dictating the levels of CHF enhancement. In all cases, titania provided for high levels of improvement, while YSZ showed similarly high levels of improvement in some cases. Pure titanium coatings exhibited lower levels of improvement, indicating qualitatively that the lower wettability on metallic substrates (as compared to oxides) may play a role in dictating CHF improvements. Titanium, however, exhibits better adhesion to metallic substrates than do oxides, which is an important property for applications in a reactor environment. Given this, the improvements in CHF achieved by titanium coatings were sufficient to justify further study.